WO1992002025A1 - Verfahren und einrichtung zum behandeln flüssiger radioaktiver abfälle - Google Patents
Verfahren und einrichtung zum behandeln flüssiger radioaktiver abfälle Download PDFInfo
- Publication number
- WO1992002025A1 WO1992002025A1 PCT/DE1991/000349 DE9100349W WO9202025A1 WO 1992002025 A1 WO1992002025 A1 WO 1992002025A1 DE 9100349 W DE9100349 W DE 9100349W WO 9202025 A1 WO9202025 A1 WO 9202025A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- condensate
- make
- amount
- waste
- container
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F26—DRYING
- F26B—DRYING SOLID MATERIALS OR OBJECTS BY REMOVING LIQUID THEREFROM
- F26B25/00—Details of general application not covered by group F26B21/00 or F26B23/00
- F26B25/22—Controlling the drying process in dependence on liquid content of solid materials or objects
Definitions
- the invention relates to a method for treating liquid radioactive waste by evaporation with condensation of the vapors, waste being replenished during the dispensing. It also refers to a facility of this kind.
- liquid radioactive operational waste is converted into a solid waste product by the thermal removal of water.
- a method of the aforementioned type is known for example from DE-PS 16 39 299.
- the fill level of the vessel in which the evaporation is carried out is determined.
- the determination is relatively imprecise and leads to insufficient filling if it is to be avoided with certainty that refilled waste overflows.
- the devices that measure the level are heavily stressed by heat and radiation and are therefore susceptible to faults.
- this object is achieved in a method of the type mentioned at the outset by measuring the amount of condensate and using this measure to control the make-up.
- the problematic direct measurement of the radioactive waste (concentrate) is achieved by the unproblematic measurement of the relatively clean condensate replaced. This measurement can take place outside the radiation range and with simple means, as will be explained in more detail later.
- a favorable embodiment of the invention consists in that the condensate is measured with a measuring vessel, especially in liters. With this level measurement, the measuring device can be emptied via a valve. The number of openings in the valve then corresponds to a certain amount of condensate; it is used to control the make-up. Alternatively, if there is even condensate, a certain amount of condensate can also be specified with a timer, which then initiates a make-up. The make-up can also be controlled according to the condensate accumulation with a timer that ensures the correct make-up.
- the evaporation is carried out discontinuously and the evaporation process is interrupted depending on the amount of condensate.
- the reduced pressure depending on the amount of condensate, can be temporarily removed by supplying air, so that the refilling can take place at normal pressure or at a pressure increased by a pump.
- the waste is advantageously fed into a closable container, in which drying then also takes place. finds.
- the level of the container is monitored.
- the fill level can be used to maintain the make-up.
- a dynamic pressure measurement is particularly suitable for this limit switch.
- a shielding container, in particular a cast iron container, with a relatively large wall thickness is preferably used as the container. It can also be an approved repository.
- a device for carrying out the method is characterized according to the invention by a measuring vessel for collecting the condensate, by a valve for the controlled discharge of the condensate from the measuring vessel and by a device for determining the amount of condensate discharged from the measuring vessel, which device is in tax connection with the refilling of waste.
- the device 1 is used for the in-line drying of liquid radioactive waste, as occurs, for example, in a nuclear power plant with a pressure or boiling water reactor. Above all, they are so-called evaporator concentrates, ie residues from the system for the treatment of radioactive waste water, which mainly consist of water-soluble salts for
- Example boric acid salts exist. Under certain circumstances, suspensions and suspensions of filter resins or the like can also be treated by the process according to the invention.
- the device 1 comprises, for example, two drying stations 2 and 3, which are arranged in a building indicated only in places, and each have a filling adapter 5 and a heater 6. You are loaded with similar barrels or shielding containers 8, which sit on transport pallets 9.
- an air film transporter 10 belongs to the device 1. Instead, it can another transport device can also be used, for example an electrically operated device or especially a rail-bound vehicle.
- each pallet 9 on which the shielding container 8 is seated is formed by an additional heater 30.
- an additional electrical heater 30 is indicated.
- steam could also be used as heating energy.
- the shielding container 8 is preferably made of cast iron. It is formed in one piece and has a base 32 and a preferably cylindrical, relatively thick shielding or side wall 33. A heater 6 rests on the side wall 33 when its two shells 35 and 36, which are pivotable in a horizontal plane in the drying station 2, 3 are attached, are folded together to form a heating jacket largely enclosing the shielding container 8.
- the filling adapter 5 has, as an outer housing, a tube 44 with a vertical axis, which is closed at its upper end with a closure cover 45 and, for example, is adjustably fastened to a compressed air or electric drive 46 in the vertical direction.
- the compressed air drive 46 is the dry Assigned to station 2 or 3 and attached to the building ceiling or a stage, for example.
- the tube 44 is the first part of a suction device for the vapors or vapors produced during drying and thickening, which are drawn off to a condenser 12 via a side connection 48 with a hose connection 49.
- the capacitor 12 is suctioned off with a water ring pump, not shown, as indicated by the arrow 14 on the line 15.
- the cooling coil 16 of the condenser 12 is connected to a cooling water system.
- the condensate is discharged from the underside of the condenser 12 through a line 18 and arrives in a collecting or measuring vessel 20 with a defined volume.
- the amount of condensate is determined in a known manner, for example by weight measurement or level measurement. If in each case the intended fill level of 1 liter is reached, the measuring vessel 20 is emptied by opening a valve 21, as indicated by the arrow 22.
- a contact 24 is provided on the valve 21, via which a timer and counter element 25 is controlled.
- An arrow 26 indicates that the make-up is controlled by the timer 25.
- connection 48 of the filling adapter 5 is diagonally opposite a connection 50 to which a hose 51 is fastened as part of a charging line. It serves for the controlled ventilation of the container 8 when the container contents are drying, that is to say the radioactive waste 52.
- the liquid radioactive waste 52 to be dried is supplied via the feed line 51, which then passes through an inlet pipe 53 which preferably runs in the middle of the pipe 44 without contact with the interior 6 walls of the housing 4 get into the shielding container 8.
- the feed which is indicated by an arrow 54, is controlled by opening a valve (not shown) depending on the amount of condensate.
- connection 50 a further connection 55 with a hose is provided on housing 4, which leads to a compressed air source (not shown).
- the compressed air indicated by a double arrow 58 is applied to a filling level measuring device 57 in the filling adapter 5, which works according to the dynamic pressure measuring principle. Measurements are only made when filling the shielding container 8.
- the dynamic pressure measurement is used for the final shutdown and for monitoring the determination of the concentrate amount according to the invention.
- the shielding container 8 is gradually filled or refilled with concentrate.
- the filling adapter 5 is lifted up off the cover 40, so that the shielding container 8 can be brought to a manipulator or a sealing station 60 with the air film transporter 10.
- the closing station 60 comprises a stopper 61 and a screwdriver 62, which are fastened next to one another, for example on the building ceiling 47 or stage. They are both preferably operated by compressed air, as indicated by arrows 63, 64 and 65. An electric drive can also be used instead.
- the stopper 61 carries out a vertical movement with a piston drive, with which a stopper 67b which is detachably fastened to a lifting part 67a is inserted into the opening 41 of the cover 40; this stopper has a T-shape on average.
- the plug 67b is fastened there with the aid of the screwdriver 62, so that a container capable of being stored in a repository is formed which is then brought with the air film transporter 10 to a transfer station (not shown). From there, the goods are transported to an interim or final storage facility.
- the stopper 61b can also be used to remove the stopper 67b from the opening 41 in the cover 40 at the start of the filling process.
- the filling adapter 5 can be structurally combined with the support 61 and / or with the screwdriver 62.
- the vapors which are produced during the drying under more or less large negative pressure are condensed, and the relatively clean condensate is collected in the collecting vessel 20 with a defined volume.
- this amount of condensate is drained off according to arrow 22 to a container or to the building sump; the number of openings of the valve 21 is registered.
- the make-up according to arrow 54 is initiated. It takes place after the system has been ventilated and is ended again by a level measurement.
- the combination of "measurement of the amount of condensate” and "timer expiry" after opening certain fittings or pending certain signals can be used to control and ensure the discontinuous make-up as well as to recognize and record the end of the drying process.
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
- Drying Of Solid Materials (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Treatment Of Sludge (AREA)
- Measurement Of Radiation (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DEP4023161.5 | 1990-07-20 | ||
DE4023161A DE4023161A1 (de) | 1990-07-20 | 1990-07-20 | Verfahren und einrichtung zum behandeln fluessiger radioaktiver abfaelle |
Publications (1)
Publication Number | Publication Date |
---|---|
WO1992002025A1 true WO1992002025A1 (de) | 1992-02-06 |
Family
ID=6410719
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/DE1991/000349 WO1992002025A1 (de) | 1990-07-20 | 1991-04-25 | Verfahren und einrichtung zum behandeln flüssiger radioaktiver abfälle |
Country Status (6)
Country | Link |
---|---|
US (1) | US5430227A (hu) |
CS (1) | CS216291A3 (hu) |
DE (2) | DE9018112U1 (hu) |
ES (1) | ES2088327B1 (hu) |
HU (1) | HU212236B (hu) |
WO (1) | WO1992002025A1 (hu) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0669171A2 (de) * | 1994-02-01 | 1995-08-30 | Binder & Co. Aktiengesellschaft | Vorrichtung zum Sortieren von Abfällen |
EP2905785A1 (de) * | 2014-02-07 | 2015-08-12 | GNS Gesellschaft für Nuklear-Service mbH | Verfahren zur Trocknung von radioaktiv belasteten Flüssig-Feststoff-Gemischen und Trocknungsbehälter |
Families Citing this family (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DK201890D0 (da) * | 1990-08-23 | 1990-08-23 | Asger Gramkow | Apparat samt fremgangsmaade til rensning af emulgerede vaesker |
DE4211012C2 (de) * | 1992-04-02 | 2000-11-23 | Bsh Bosch Siemens Hausgeraete | Verfahren und Vorrichtung zum Steuern eines Trocknungsvorganges |
DE4307844C2 (de) * | 1993-03-12 | 1996-09-12 | Hansa Projekt Anlagentechnik G | Anordnung an einer Trockenkammer für die Aufnahme eines Fasses mit kontaminiertem Schlamm |
WO1996010830A1 (de) * | 1994-10-04 | 1996-04-11 | Siemens Aktiengesellschaft | Trocknungsstation für flüssigen oder feuchten abfall |
AT509771B1 (de) * | 2010-04-15 | 2012-03-15 | Hubert Ing Knoth | Einrichtung zum trocknen eines maschinenteils |
RU2477538C1 (ru) * | 2011-12-06 | 2013-03-10 | Открытое акционерное общество "Ведущий научно-исследовательский институт химической технологии" | Способ очистки жидких радиоактивных отходов и установка для его осуществления |
CN108062990B (zh) * | 2018-01-11 | 2024-06-07 | 航天晨光股份有限公司 | 一种放射性废液结晶干燥系统及其方法 |
CN112992398A (zh) * | 2021-02-08 | 2021-06-18 | 乔冕 | 一种放射性废水多级处理装置 |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4030708A (en) * | 1973-10-25 | 1977-06-21 | Stock Equipment Company | Process for introducing particulate material into a container |
US4234448A (en) * | 1976-11-01 | 1980-11-18 | Hitachi, Ltd. | Method and apparatus for treating radioactive waste |
Family Cites Families (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2165510A1 (de) * | 1971-12-30 | 1973-08-16 | Kernforschungsanlage Juelich | Einrichtung zum verfestigen fluessiger radioaktiver rueckstaende |
DE2819085C3 (de) * | 1978-04-29 | 1981-04-23 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Verfahren zur endlagerreifen, umweltfreundlichen Verfestigung von hoch- und mittelradioaktiven und/oder Actiniden enthaltenden, wäßrigen Abfallkonzentraten oder von in Wasser aufgeschlämmten, feinkörnigen festen Abfällen |
DE2844608A1 (de) * | 1978-10-13 | 1980-04-30 | Hoechst Ag | Verfahren zum lagern fluessiger, radioaktiver abfallstoffe |
US4409137A (en) * | 1980-04-09 | 1983-10-11 | Belgonucleaire | Solidification of radioactive waste effluents |
DE3029147A1 (de) * | 1980-07-31 | 1982-02-25 | Kraftwerk Union AG, 4330 Mülheim | Verfahren und anlage zur behandlung radioaktiver rueckstaende aus borathaltigen abwaessern |
DE3321063A1 (de) * | 1983-06-10 | 1985-01-24 | Kraftwerk Union AG, 4330 Mülheim | Probensammeleinrichtung fuer gas- oder dampffoermige kondensierbare radioaktive stoffe, insbesondere zum sammeln von tritiumspuren |
DE3432103A1 (de) * | 1984-08-31 | 1986-03-13 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zum volumenreduzierung von radioaktiv beladenen fluessigkeiten und rippenkoerper zur verwendung dabei |
US4800042A (en) * | 1985-01-22 | 1989-01-24 | Jgc Corporation | Radioactive waste water treatment |
-
1990
- 1990-07-20 DE DE9018112U patent/DE9018112U1/de not_active Expired - Lifetime
- 1990-07-20 DE DE4023161A patent/DE4023161A1/de not_active Ceased
-
1991
- 1991-04-25 HU HU9300137A patent/HU212236B/hu not_active IP Right Cessation
- 1991-04-25 ES ES09250012A patent/ES2088327B1/es not_active Expired - Fee Related
- 1991-04-25 WO PCT/DE1991/000349 patent/WO1992002025A1/de active IP Right Grant
- 1991-07-12 CS CS912162A patent/CS216291A3/cs unknown
-
1993
- 1993-01-21 US US08/007,053 patent/US5430227A/en not_active Expired - Lifetime
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4030708A (en) * | 1973-10-25 | 1977-06-21 | Stock Equipment Company | Process for introducing particulate material into a container |
US4234448A (en) * | 1976-11-01 | 1980-11-18 | Hitachi, Ltd. | Method and apparatus for treating radioactive waste |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0669171A2 (de) * | 1994-02-01 | 1995-08-30 | Binder & Co. Aktiengesellschaft | Vorrichtung zum Sortieren von Abfällen |
EP0669171A3 (de) * | 1994-02-01 | 1996-02-28 | Binder Co Ag | Vorrichtung zum Sortieren von Abfällen. |
EP2905785A1 (de) * | 2014-02-07 | 2015-08-12 | GNS Gesellschaft für Nuklear-Service mbH | Verfahren zur Trocknung von radioaktiv belasteten Flüssig-Feststoff-Gemischen und Trocknungsbehälter |
Also Published As
Publication number | Publication date |
---|---|
CS216291A3 (en) | 1992-02-19 |
ES2088327A1 (es) | 1996-08-01 |
DE4023161A1 (de) | 1992-01-23 |
US5430227A (en) | 1995-07-04 |
HU9300137D0 (en) | 1993-09-28 |
HU212236B (en) | 1996-04-29 |
HUT71176A (en) | 1995-11-28 |
DE9018112U1 (de) | 1995-06-29 |
ES2088327B1 (es) | 1997-02-01 |
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